Text

Monthly Operating Repts for Jul 1983
	ML20077J395
Person / Time
Site:	Quad Cities
Issue date:	08/01/1983
From:	Kalivianakis, Misak A; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
	NJK-83-267, NUDOCS 8308160346
	Download: ML20077J395 (26)
	v • d • e

C

+

QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT JULY 1983 CCHMONWEALTH EDIS0N COMPANY AND IOWA-ILLINOIS CAS & ELECTRIC COMPANY NRC DOCKET NOS, 50-254 AND 50-265 LICENSE NOS, DPR-29 AND DPR-30 83081603g600 54 PDR ADOC PDR R

fEf III

TABLE OF CONTENTS I,

Introduction II, Summary of,0perating Experience A.

Unit One B,

Unit Two III, Plant or Procedure Changes, Tests, Experiments, and Safety Related Maintenance A,

Amendments to Facility License or Technical Specifications B.

Facility or Procedure Changes Requiring NRC Approval C,

Tests and Experiments Requiring NRC Approval D.

Corrective Maintenance of Safety Related Equipment IV, Licensee Event Reports

.V, Data Tabulations A,

Operating Data Report B,

Average Daily Unit Power Level C,

Unit Shutdowns and Power Reductions VI, Unique Reporting Requirements A,

Main Steam Relief Valve Operations B,

Control Rod Drive Scram Timing Data

VII, Refueling Infonnation VIII, Glossary t

\\

I, INTRODUCTION Quad-Cities Nuclear Power Station is composed of two Bolling Water Reactors, each with a Maximum Dependable Capacity of 769 MWe net, located in Cordova, Illinois.

The Station is jointly owned by Commonwealth Edison Company and lowa-Illinois Gas & Electric Company. The Nuclear Steam Supply Systems are General Electric Company Boiling Water Reactora. The Architect / Engineer was Sargent & Lundy, Incorporated, and the primary construction contractor was United Engineers & Constructors. The condenser cooling method is a closed cycle spray canal, and the Mississippi River is the condenser cooling water source. The plant is subject to license numbers DPR-29 and DPR-30, issued October 1,1971, and March 21, 1972, respectively, pursuant to Docket Numbers 50-254 and 50-265. The date of initial reactor criticalities for Units 1 and 2 respectively were October 18, 1971, and April 26, 1972.

Commercial generation of power began on February 18, 1973 for Unit

- 1 and March 10, 1973 for Unit 2.

This report was complied by Becky Brown and Alex Misak, telephone number 309-654-2241, extensions 127 and 194.

t r

t 4

7 c- -

e, b

r-g

+

d--~

t

II,

SUMMARY

OF OPERATING EXPERIENCE A.

Unit One Unit One continued operating at a reduced power level of 770 MWe throughout the month due to the IDI Feedwater Heater being out of service.

July 1-8: On July 3, Unit One dropped load to 400 MWe to cool the Suppression Chamber and perform weekly Turbine tests. At 0830 hours0.00961 days 0.231 hours 0.00137 weeks 3.15815e-4 months , on July 4, the unit increased load to 650 MWe as requested by the Load Dispatcher. At 0415 hours0.0048 days 0.115 hours 6.861772e-4 weeks 1.579075e-4 months , on July 5, the unit began increasing load normally to 770 MWe.

July 9-15: At 0100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months , on July 9, the unit dropped load to perform weekly Turbine tests.

Following the tests, the unit dropped load to 400 MWe to cool the Suppression Chamber.

At 1320 hours0.0153 days 0.367 hours 0.00218 weeks 5.0226e-4 months , on July 10, the unit increased load to 650 MWe as requested by the Load Dispatcher. At 1900 hours0.022 days 0.528 hours 0.00314 weeks 7.2295e-4 months , the unit began increasing load normally to 770 MWe.

July 16-22: At 2215 hours0.0256 days 0.615 hours 0.00366 weeks 8.428075e-4 months , on July 16, the unit dropped load to perform weekly Turbine tests. After the tests were completed, the unit dropped load to 400 MWe for Suppression Chamber cooling. At 2200 hours0.0255 days 0.611 hours 0.00364 weeks 8.371e-4 months , on July 17, open cycle cooling was initiated, and at 0600 hours0.00694 days 0.167 hours 9.920635e-4 weeks 2.283e-4 months , on July 18, the unit began increasing load to 770 MWe.

At 1620 hours0.0188 days 0.45 hours 0.00268 weeks 6.1641e-4 months , on July 18, open cycle cooling was terminated. At 1530 hours0.0177 days 0.425 hours 0.00253 weeks 5.82165e-4 months , on July 20, open cycle cooling commenced and continued until 1700 hours0.0197 days 0.472 hours 0.00281 weeks 6.4685e-4 months on July 22.

July 23-31: At 0330 hours0.00382 days 0.0917 hours 5.456349e-4 weeks 1.25565e-4 months , on July 23, the unit dropped load to 715 MWe to perform weekly Turbine tests, and remained at this power level as requested by the Load Dispatcher. At 1740 hours0.0201 days 0.483 hours 0.00288 weeks 6.6207e-4 months , the unit dropped load to 595 MWe as requested by the Load Dispatcher. At 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months , on July 25, the unit began increasing load to 720 MWe. The unit held load at this level in preparation for a special Xenon Transient test to be perforned on July 27 At 0803 hours0.00929 days 0.223 hours 0.00133 weeks 3.055415e-4 months , on July 27, load was reduced to 620 MWe as per the special test.- At 1100 hours0.0127 days 0.306 hours 0.00182 weeks 4.1855e-4 months , the special test was terminated due to high Suppression Chamber temperature, and the unit dropped load to 400 MWe for Suppression Chamber cooling.

At-1445 hours, open cycle cooling commenced, and at 1930 hours0.0223 days 0.536 hours 0.00319 weeks 7.34365e-4 months , the unit began increasing load to 770 MWe. At 2100 hours0.0243 days 0.583 hours 0.00347 weeks 7.9905e-4 months , on July 29, open cycle cooling was terminated, and the unit continued operating at 770 MWe until 0230 hours0.00266 days 0.0639 hours 3.80291e-4 weeks 8.7515e-5 months on July 30 when the unit dropped load to 600 MWe due to low Service Water pressure.

i r

{

l ij

B.

Unit Two Unit.Two continued operation throughout the month derated due to end of cycle fuel depletion.

July 1-8: Unit Two began the month operating at a load of 525 MWe and operated at this load until 0545 hours0.00631 days 0.151 hours 9.011243e-4 weeks 2.073725e-4 months on July 2, whoo the unit dropped load to 350 MWe as requested by the Load Dispatcher. At 0915 hours0.0106 days 0.254 hours 0.00151 weeks 3.481575e-4 months , the unit increased load to maximum. At 0000 hours0 days 0 hours 0 weeks 0 months , on July 3, the unit dropped load to 300 MWe for Suppression Chamber cooling.

At 0630 hours0.00729 days 0.175 hours 0.00104 weeks 2.39715e-4 months , on July 5, the unit began increasing load normally to maximum.

July 9-15: At 0115 hours0.00133 days 0.0319 hours 1.901455e-4 weeks 4.37575e-5 months , on July 9, the unit dropped load to 300 MWe for Suppression Pool cooling. At 1030 hours0.0119 days 0.286 hours 0.0017 weeks 3.91915e-4 months , on' July 10, the unit increased load normally to maximum.

July 16-22: At 2215 hours0.0256 days 0.615 hours 0.00366 weeks 8.428075e-4 months , on July 16, the unit dropped load to 300 MWe for Suppression Pool cooling. At 1930 hours0.0223 days 0.536 hours 0.00319 weeks 7.34365e-4 months , on July 17, the unit dropped load further to 200 MWe.

At 2200 hours0.0255 days 0.611 hours 0.00364 weeks 8.371e-4 months , open cycle cooling i

was _ initiated, and the unit began increasing load to maximum at 0630 hours0.00729 days 0.175 hours 0.00104 weeks 2.39715e-4 months , on July 18, 1983 At 1620 hours0.0188 days 0.45 hours 0.00268 weeks 6.1641e-4 months , open cycle cooling was terminated. At 1530 hours0.0177 days 0.425 hours 0.00253 weeks 5.82165e-4 months , on July 20, open cycle cooling commenced and continued until 1700 hours0.0197 days 0.472 hours 0.00281 weeks 6.4685e-4 months on July 22.

July 23-31: At 0100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months , on July 23, the unit dropped load to 230 MWe as requested by the Load Dispatcher. At 0330 hours0.00382 days 0.0917 hours 5.456349e-4 weeks 1.25565e-4 months , load was increased to 280 MWe. At 0945 hours0.0109 days 0.263 hours 0.00156 weeks 3.595725e-4 months , on July 25, the unit increased

)

load to 425 MWe as requested by the Load Dispatcher. At 1530 hours0.0177 days 0.425 hours 0.00253 weeks 5.82165e-4 months , the unit began dropping load to match the Unit One load increase, thereby maintaining a constant Station load. At 0755 hours0.00874 days 0.21 hours 0.00125 weeks 2.872775e-4 months , on July 26, the unit increased load to 440 MWe.

At 0825 hours0.00955 days 0.229 hours 0.00136 weeks 3.139125e-4 months , on July 27, the unit increased load to 495 MWe, and maintained that load until 1100 hours0.0127 days 0.306 hours 0.00182 weeks 4.1855e-4 months , when the unit dropped load to 320 MWe to cool the Suppression Chamber. At 1445 hours0.0167 days 0.401 hours 0.00239 weeks 5.498225e-4 months , open cycle cooling was commenced, and at 1945 hours0.0225 days 0.54 hours 0.00322 weeks 7.400725e-4 months load was increased to 495 MWe.

At 2100 hours0.0243 days 0.583 hours 0.00347 weeks 7.9905e-4 months , on July 30, the unit dropped load to 300 MWe due to low Service Water pressure.

4 m

w n

m

-4.

-w-

,ww-

--ap

-r y

ng y a

III,, PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE A.

Amendments to Facility License or Technical Specifications There were no Amendments to the Facility License or Technical Specifications for the reporting period.

B.

Facility or Procedure Changes Requiring NRC Approval There were no Facility or Procedure changes requiring NRC approval for the reporting period.

C.

Tests and Experiments Requiring NRC Approval There were no Tests or Experiments requiring NRC approval for the reporting period.

D.

Corrective Maintenance of Safety Related Equipment The following represents a tabular summary of the safety related maintenance performed on Unit One and Unit Two during the reporting period. This summary includes the following headings:

W rk Request Numbers, LER Numbers, o

Components, Cause of Malfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.

t UNIT ONE HAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS ~

.W.R.

LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT HALFUNCTION SAFE OPERATION PREVENT REPETITION Q26812 1-1001-34B Valve The Limitorque operator The

'B' loop was The operator was would not manually declared inoperable repaired.

engage.

while the work was pe r fo rmed, ar.d t he required surveillances

~

were performed on the

'A' loop.

Q26956 RHR Heat The motor operator The valve was cracked The limits of the Exchanger Bypass position sensors were off the seat. Then it motor operator Valve - M0 slightly off.

opened and closed position sensor were l

i001-16B) from the Control Room.

adjusted.

Q27029 83-26/03L Main Steamline The meter drif ted out The other meters were The meter was DP meter 1-261-of calibration.

reading correctly. A recalibrated and 25 was reading Group i Iso:ction would returned to service.

lower than have occurred on high othe rs. It was flow.

reca l i b ra ted.

Q25189 LPRM 16-33B The 04 transitor &

While doing the Rod The dual trip unit G3 integrated circuit Block Monitor Instru-board 28 was repaired.

failed.

ment Maintenance Surveillance, bypassing LPRM 16-33B had no ef fect on the count and inoperable trips. The other LPRMS were operable.

G M

y UNIT ONE MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS

.W.R.

LER.

NUMBER NUMBER

'0F ON ACTION TAKEN TO COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION ~

027082 83-27/03L 1/2 Diesel There was intermittent This switch is not The switch was Generator Fuel high current through requi red for operation replaced.

Prime Pump Push-the switch.

of the pump. While the button switch switch was being repaired,.the Diesel Generator was inoperable for the monthly mainte-nance. The required surveillances were pe r fo rmed.

Q27134 M0-1-2301-48 The end bell on the The M0-1-2301-48 was A new motor was l'

HPCI Normal drive end of the taken.out of service in installed on the Cooling Return motor was broken, the open position, in ope ra to r.

Valve the event HPCI Cooling Return was required.

1 Q26437 IB RHR Service The inboard seal on The 'B' loop of RHR was The bearings were Water Booster the pump was leaking declared inoperable, inspected and Pump 1-1001-65B badly.

while the work was replaced; the well being performed, and the water to stuffing box required surveillances line was repaired, were perforned on the and the pump stuffing

'A' loop.

was repacked.

Q26706 83-25/03L Suppression The stem was bent.

The valve appeared to The stem was Chamber Test &

open, but would not straightened in place Spray Valve clear the dual with heat & force.

indication in the This was a temporary Control Room. The valve fix. The stem will be was declared inoperable replaced at the next while the work was Unit One refueling perforned and the outage.

required surveillances

' ~

were performed on the

'A' loop.

'I

1 UNIT ONE MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NUMBER NUM8ER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q27247 83-28/03L Suppression Chamber Failed breaker.

The breaker tripped The breaker was Containment

- approximately every replaced.

Cooling Valve third time the valve 1-1001-36A was operated. The required surveillances

~ were performed while the 'A' loop was in-ope rabl e.

Q27358 Core Spray The breaker was The breaker tripped The breaker was Pump Outboard tripping at 85 when the valve was replaced.

Discharge amps instead of originally opened, Valve 1-1402-125 amps.

but after the breaker 25A was reset the valve worked fine.

O

?

UNIT TWO MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT HALFUNCTION SAFE OPERATION PREVENT REPETITION Q26995 LPRM 16-25A Bad LPRM Logic Card.

The inoperative light The card was replaced, on 902-37 panel was lit. This did not affect the operation of the APRM.

- Q29807 83-II/03L Suppression The circuit breaker The motor bearings

'Chambe r Cool ing tripped wnen the and pinion gear were

& Test Valve valve was given an replaced.

2-1001-36B open signal. Then worked fine af ter the breaker was reset.

The 'B' loop was declared inoperable, and the required surveillances were done on the

'A' loop.

Q27141 2D RHR Service -

The top vent was The loop was declared The vent line was Water Pump cracked.

Inoperable while work replaced.

2D-1002 was performed. The requi red surveillances were done on the other loop.

Q27434 2B RilR Room The interlock device The associated 'A' loop The interlock device Door on the door was out was declared inoperative was adjusted and the of adjustment.

and the requi red RHR

'A' loop returned surveillances were to service.

performed on the other loop.

~

e

- -. - ~

IV, LICENSEE EVENT REPORTS The following is a tabular summary of _all licensee event reports for Quad-Cities Units One and Two occurring during the reporting period, pursuant to the reportable occurrence reporting requirements as set forth in sections 6.6.B.1. and 6.6.B.2. of the Technical

. Specifications.

UNIT ONE Licensee Event Report Number Date Title of Occurrence 83-26/03L 7-5-83 Main Steam Line High Flow Switch Drift 83-27/03L 7-6-83 1/2 Diesel Generator Fuel Prime Pushbutton Failure 83-28/03L 7-15-83 1A Containment Cooling Loop inoperable 83-29/03L 7-11-83 IB RHR Service Water Pump inoperable 83-31/03L 7-27-83 Two Firestops Found Damaged' i

UNIT TWO 83-il/03L 7-11-83 MO 2-1001-36B Valve Tripped l

[

t l

e

. +,

-+

2 e,

k 1

l.

V, DATA TABUIATIONS The following data tabulations are presented in this report:

' A, Operating Data Report B,

Average Daily Unit Power Level C,

Unit Shutdowns and Power Reductions J

I A.

1 I..

b 4

l i

t t

g 4

,.Eh-,--,

I > w - r--= ww w e w w-* m -t e w

- s* +-w ww w -,

e-- a r

= v e =N'

' w-e

-w.

==--r--

-~ev'e

OPERATING DATA REPORT DOCKET NO.

50-254 UNIT ONE DATEAvoust 2 f

COMPLETED BYAlex L. Misok TELEPHONE 309-654-2241xi94 OPERATING STATUS l

0000 070183 I

1. Reporting period:2400 073183 Gross hours in reporting period:

744

2. Currently authorized power level (MWt): 2511 Max. Depend capacity (MWe-Net): 769* Design electrical roting (MWe-Net): 789

3. Power level to which restricted (if any)(MWe-Net): NA

4. Reasons for restriction (if any):

This Month Yr.to Date Cumulative

5. Nunber of hours reactor was critical 744.0 4879.6 80050.0

6. Reactor reserve shutdown hours 0.0 0.0 3421.9

7. Hours generator on line 744.0 4839.5 76926.2

8. Unit reserve shutdown hours.

0.0 0.0 909.2

9. Gross thermal energy generated (HWH) 1621849 11462942 157675933

10. Gross electrical energy generated (MWH) 507886 3729116 50850997 ii. Het electrical energy generated (MWH) 476714 3510507 47339415

12. Reactor service factor 100.0 95.9, 81.4

13. Reactor ovellobility factor 100.0 95.9 84,8

14. Unit service factor 100.0.

95.i 78.2 l

15. Unit avo11ob111ty factor 100.0 95.1 79.i

16. Unit capacity factor (Using MDC) 83.3 89.7 62.6

17. Unit capacity factor (Using Des.MWe) 81.2 uB7.5 61.0

18. Unit forced cutoge rate 0.0 1.5 6.4

19. Shutdowns scheduled over next 6 months (Type,Date,ond Duration of each):

20. If shutdown at end of report period, estimated date o f s t or t u p _____ N A______

$The litC not be lever then 70 llle dering periods of high onblent tenperatore due to the thernal perfernance of the sprey canel.

8U110FFICIAL COMPANY lulIDS ARE USD Ill THIS REPORT

OPERATING DATA REPORT DOCKET NO.

50-265 UNIT TWO DATEAuoust 2 COMPLETED BYAlex L.

Misak TELEPHONE 309-654-2241x194 OPERATING STATUS 0000 070183

1. Reporting period 2400 073183 Gross hours in reporting period 744

2. Currcatly authorized power level (MWt): 2511 Mox. Depend copocity (MWe-Net): 769* Design electrical rating (MWe-Net): 789

3. Power level to which restricted (if any)(MWe-Net): NA 4.

Reasons for restriction (if any):

This Month Yr.to Date Cunulative

5. Number of hours reactor was critical 744.0 4823.0 77086.4

6. Reactor reserve shutdown hours 0.0 0.0 2985.8

7. Hours generator on line 744.0 4793.7 74381.8 8.

Unit reserve shutdown hours.

0.0 0.0 702.9 9.

Gross thernal energy generated (MWH) 1090988 9678146 154269640

10. Gross electrical energy generated (HWH) 324910

__ 3064324 49101859

11. Het electrical energy generated (MWH) 299399 2862006 46045573

12. Reactor service factor 100.0 94.8 79.1

13. Recctor avo11obility factor 100.0 94.8 82.2

14. Unit service factor 100.0 94.2 76.3

15. Unit ovullability factor 100.0 94.2 77.0

16. Unit capacity factor (Using MDC) 52.3 73.2 61.4

17. Unit copocity factor (Using Des.MWe) 51.0 71.3 59.9

18. Unit forced outage rate 0.0 2.2 8.7

19. Shutdowns scheduled over next 6 nonths (Type,Date,and Duration of each):

20. If shutdown at end of report period, estimated date o f s t ar t u p

____N A________

\\

The MDC my be lever than 769 MWe dering perleds of high unblent tenperatsre det to the thernal performnce of the sprey canal.

$UN0FFICIAL COMPANY NUMBERS ARE USED IN THIS REPORT

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-254 UNIT ONE DATEAuaust 2 COMPLETED BYAlex L.

Misak TELEPHONE 309-654-2241xi94 MONTH Jelv 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Het) 1.

725.7 17, 387.5 2.

708.2 18.

585.1 3.

387.8 19.

720.2 4.

528.3 20.

706.7 5.

653.4 21.

740.3 6.

723.3 22.

743.1 7.

714.1 23, 613.2 8.

722.8 24.

578.8 9.

412.3 25.

603.1 10, 516.8 26.

671.3 11.

686.5 27.

542.1 12, 722.9 28.

704.8 13, 720.7 29.

731.4 14, 720.7 30.

585.3 15.

722.8 31, 570.3 16, 713.8 INSTRUCTIONS On this forn list the average delly enit pwer level in Mile-tiet for each day in the reporting unth. Compete to the terest uhele a g,eustt.

n Then figeres vill be sud to plot a ereph for each reporting math. Note that when noniner. dependable copecite is sud for the net electrical rating of the enit there ney be occasions when the delly estrage pwer level exceeds the illI line (or the restricted pwer level line),.In sech caus,the estrege dolly enit puer setpet sheet should be festnoted to explain the apparent aneely

~.

APPENDIX D AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-265 UNIT TWO DATEAvaust 2 COMPLETED BYAlex L. Misak TELEPHONE 309-654-2241xi94 MONTH Julv 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

485.0 17, 259.3 2.

449.0 18, 395.6 3.

289.8 19.

460.8 4.

283,5 20.

441.2 5.

463.3 21, 462.0

-6.

487.9 22.

464.0 7.

471.9 23.

282.6 8.

475.0 24, 293.5 9.

291.4 25, 322.8 10, 410.i 26.

365.9 11.

477.9 27.

370.8 12, 459.6 28.

469.2 13, 456.7 29.

447.9 14.

452.8 30, 306.5 15.

448.8 31.

288.5 16.

441.7 INSTRUCTIONS On this forn list the overage daily enit pwer level in mie-Met for each day in the reputing nenth.Cupete to the eerest uhele neg, matt.

n These figeres will be esed to plot e ereph for each repeting nonth. Note tnet when notinen dependeble copecity is used fu the net electrical rating of tne snit there ney be occasions when the delly eteroge power level excee4s the illi line (w the restricted pwer level line).,In such cases,the everage daily enit power outpet sheet shecid he feetnoted to explsin the apparent onenely

m m

nas sum una see men use man men ums una r,

r,. r m n,

ID/5A APPENDIX D QTP 300-S13 UNIT SilHTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO. 050-254 August 1982 UNIT NAME Quad-Cities Unit One CoffPLETED BY Alex Misak DATE August 8, 1983 REPORT HONTil JULY 1983 TELEPil0NE 309-6S4-2241 E

N m

=

et hh g

g

{

LICENSEE h

EVENT U

o" m

DURATION w

NO.

DATE (IlOURS)

REPORT NO.

CORRECTIVE ACTIONS /CotitlENTS o

83-40 830703 S

0.0 D

5 SA VESSEL Reduced load to cool Suppression Chamber 83-41 830709 S

0.0 B

5 HA XXXXXX Reduced load to perform weekly Turbine tests 83-42 830709 S

0.0 D

5 SA VESSEL Reduced load to cool Suppression Chamber 83-43 830716 S

0.0 8

5 HA XXXXXX Reduced load to perform weekly Turbine tests 83-44 830717 S

0.0 D

5 SA VESSEL Reduced load to cool Suppression Chamber 83-45 830723 S

0.0 F

5 EA ZZZZZZ Load reduction requested by Load Dispatcher due to low system demand 83-46 830723 S

0.0 F

5 EA ZZZZZZ Load reduction requested by Load Dispatcher due to low system demand i

83-47 830727 S

0.0 B

5 RC FUELXX Reduced load to perform special Xenon test 83-48 830727 5

0.0 F

5 EA ZZZZZZ Load reduction requested by Load Dispatcher due to low APPROVED system demand AUG 1 G 1982 (final) ygg3g

M M

M qM M

M M

M

n. n p

ID/SA APPENDIX D QTP 300-S13 UNIT SiltlTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO. 050-254 August 1982 UNIT NAME Quad-Cities Unit One COtlPLETED BY Alex Hisak DATE August 8, 1983 REPORT tl0NTil JULY 1983 TEI.EPHONE 309-654-2241 p

N w"

5 UE gw@

dm I

~

Q M

LICENSEE m

DURATION d

EVENT gu v

w 0

NO.

DATE (IIOURS) d REPORT NO.

CORRECTIVE ACTIONS /C0titIENTS u

i ca 83-49 830730 S

0.0 Il 5

WA ZZZZZZ Reduced load due to low Service Water Pressure 83-50 830730 S

0.0 H

5 WA ZZZZZZ Reduced load due to low Service Water Pressure l

l APPROVED AUG 1 G 1982 (final) ygo3g

M M

M q

M M

M

n. n p

ID/5A APPENDIX D QTP 300-S13 UNIT SilUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO.

050-265 August 1982 UNIT NAME Quad-Cities Unit Two COMPLETED BY Alex Misak DATE August 8, 1983 pgpog7 gog7;g JULY 1983 TELEPil0NE 309-654-2241 N

H w "'

~

5 gw

$w d$

LICENSEE v3 @

DURATION EVENT o"

H w

g "' g u

NO.

DATE (IIOURS)

REPORT NO.

CORRECTIVE ACTIONS / COMMENTS o

ca 83-45 830702 S

0.0 F

5 EA ZZZZZZ Load reduction requested by Load Dispatcher due to low system demand 83-46 830703 S

0.0 D

5 SA VESSEL Reduced load to cool Suppression Chamber 83-47 830709 5

0.0 D

5 SA VESSEL Reduced load to cool Suppression Chamber 83-48 830716 S

0.0 F

5 EA ZZZZZZ Load reduction requested by Load

' Dispatcher due to low system demand 83-49 830717 S

0.0 D

5 SA VESSEL Reduced load to cool Suppression Chamber 83-50 830723 S

0.0 F

5 EA ZZZZZZ Load reduction requested by Load Dispatcher due to low system demand 83-51 830725 S

0.0 F

5 EA ZZZZZZ Reduced load to match Unit 1 increase to maintain constant Station load as requested by Load Dispatcher 83-52 830727 S

0.0 D

5 SA VESSEL Reduced load to cool Suppression Chamber

~

83-53 830730 S

0.0 H

5 WA ZZZZZZ Reduced load due to low Service Water Pressure APPROVED AUG 1 G 1982 (final) ygg3g

m M

F""1 rT M

M M

n M.

n p

1D/5A APPENDIX I)

QTP 300-S13 llNIT SIIUTDOWNS AND POWER REDilCTIONS Revision 6 DOCKET NO. E0-26t; August 1982 COMPLETED BY Alex Misak UNIT NAME Ouad-Cities Unit _Iwo DATE August 8. 1983 HEPORT MONTil JULY l_983 TELEPil0NE 309-654-2241 l

p N

w"

~

5 aSE gw hi m f

Q M

LICENSEE m8 8

(

O DURATION d

EVENT u

o w

No.

DATE (Il0URS)

REPORT NO.

COHRECTIVE ACTIONS /COMilENTS I

U a

j 83-54 830730 S

0.0 H

5 WA ZZZZZZ Reduced load due to low Service Water l

Pressure 83-55 830730 S

0.0 H

5 WA ZZZZZZ Reduced load due to low Service Water Pressure l

l l

L k

/

1 i

APPROVED AUG 1 G 1982

-i-(rinai) yco3g

l VI, UNIQUE REPORTING REQUIREMENTS The following items are included in this report based on prior cemitments to the conmission:

A, MAIN STEAM RELIEF VALVE OPERATIONS There were no Main Steam Relief Valve Operations for the reporting period.

B.

CONTROL ROD DRIVE SCRAM TIMING DATA EUR UNITS ONE AND '1WO There was no Control Rod Drive Scram Timing Data for Units One and Two for the reporting period.

I l

l

VII, REFUELING INFORMATION The following information about future reloads at Quad-CLties Station was requested in a January 26, 1978, licensing memorandtmn (78-24) from D, E, O'Brien to C, Reed, et al., titled "Dresden, j

Quad-Cities, and Zion Station--NRC Request for Refueling Infonnation",

dated January 18, 1978 i

a 4

4 2

I

~9 w

n, -

o n

s-r n

- r

e QTP 300-S32 R:; vision 1

[.

QUAD-CITIES REFUELING M rch 1970

(

INFORMATION REQUEST r.

1.

Unit:

Q1 Reload:

6 Cycle:

7 m

2.

Scheduled date for next refueling shutdown:

9-6-82 3

Scheduled date for restart following refueling:

12-18-82

'F 4.

Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment:

Yes 5.

Scheduled date(s) for submitting proposed licensing acticn and supporting

]

Information:

8-19-82: Tech. Spec. changes submitted to the NRC.

W 6.

Important IIcensing considerations associated with refueling, e.g., new or

' different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

a) All TxT fuel assemblies vill be removed from the core.

l b) MAPLEGR curves for fuel types in the core are being extended to h0,000 MWD /ST.

c) l(s MCPR limits vill be detemined by GE's ODYN computer code.

d) The vessel pressure safety limit is being modified to accommodate the b'

potential for higher reactor pressures as ' alculated by 0DYN.

c l

7 The number of fuel assemblies.

~

a.

Number of assemblies la core:

724 b.

Number of assemblies in spent fuel pool:

800 8.

The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned in number of fuel assemblies:

a.

Licensed storage capacity for spent fuel:

3657 b.

Planned increase in IIcensed storage:

0 9

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: 2003 XPPROVED v

- APR 2.01978 a

Q.C.O.S.R.

j

QTP 300-S32 Rsvision 1 o

k QUAD-CITIES REFUELING March 1978

-b INFORMATION REQUEST ~

s 1.

Un i t : -

Q2 Reload:

6 Cycle:

7 0

2.

Scheduled date for next refueling shutdown:

9-5-83 3.

Scheduled date for restart following refueling:

11-12-83 a

4.

b W111' refueling or resumption of operation thereaf ter require a technical specification change or other IIcense amendment:

No, however, a change to the Technical Specifications is being submitted a

(see below).

g 5.

Scheduled date(s) for submitting proposed licensing action and supporting

?

Information:

June 14, 1983 (Scheduled)

?

6.

Important IIcensing considerations associated with refueling, e.g., new or

' different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

3 a)

All new fuel assemblies will be of barrier design; MAPLHGR curves will be re-labeled to include the barrier designation.

b)

The use of ifnproved assumptions in the load reject without bypass analysis resulted in a much improved MCPR operating limit.

Technical Specifications are being changed to provide this additional operating margin.

d b

7 The number of fuel assemblies.

a.

Number of assemblies in core:

724 b.

Number of assemblies in spent fuel pool:

204 8.

The present licensed spent fuel pool storage capacity and the size of any increase.in licensed storage capacity that has been requested or is planned in number of fuel assemblies:

a.

Licensed storage capacity for spent fuel:

3897 0

b.

Planned increase in IIcensed storage:

9 The projected date of the last refueling that can be discharged' to the spent fuel pool assuming the present licensed capacity: 2003 WPPROVED

, APR 2 01978 a

Q.C.C.S.R.

L

......__.m~

_ : _.m

~_

o VIII, GLOSSARY The following abbreviations which may have been used in the Monthly Report, are defined below:

Atmospheric Containnent Atmospheric Dilution / Containment ACAD/ CAM Atmospheric Monitoring American National Standards Institute ANSI APRM Average Power Range Monitor ATWS Anticipated Transient Without Scram BWR Bolling Water Reactor Control Rod Drive CRD EHC Electro-Hydraulic Control System EOF Emergency Operations Facility GS EP Generating Stations Emergency Plan HEPA High-Ef ficiency Particulate Filter HPCI High Pres sure Coolant Injection System HRSS High Radiation Sampling System Integrated Primary Containment Leak Rate Test IPCLRT IRM Intermediate Range honitor ISI Inservice Inspection Licensee Event Report LER LLRT Local Leak Rate Test LPCI Low Pressure Coolant Injection Mode of RHRS LPRM Local Power Range Monitor MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MFLCPR Maximum Fraction Limiting Critical Power Ratio Maximum Permissible Concentration MPC MSIV Main Steam Isolation Valve NIOSH National Institute for Occupational Safety and Health Primary Containment Isolation PCI PCIOMR Preconditioning Interim Operating Management Recommendations RBCCW Reactor Building Closed Cooling Water System RBM Rod Block Monitor RCIC Reactor Core Isolation Cooling System RHRS Residual Heat Removal System RPS Reactor Protection System Rod Worth Minimizer RRM SBGTS Standby Gas Treatment System SBLC Standby Liquid Control Shutdown Cooling Mode of RHRS SDC SDV Scram Discharge Volume SRM Source Range Monitor TBCCW Turbine Building Closed Cooling Water System Traversing Incore Probe TIP Technical Support Center TSC

[C'x) Commonwalth Edison Outd Citits Nuctrar Pow 1r Station

(

77; g 22710 206 Avenue North

\\

j Cordova, tilinois 61242

(/

Telephone 309/654-2241 NJK-83-267 August 1, 1983 Director, Of fice of Inspection & Enforconent United States Nuclear Regulatory Ccomission Wa shing t on, D, C. 20555 Attention: Document Control Desk Centlemen:

Enclosed for your information is the Monthly Performance Report covering the operation of Quad-Cities Nuclear Power Station, Units One and Two, during the month of July 1983.

Very truly yours, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION

/l lelat '/

/

,s N

J, Kallvianakis Station Superintendent bb Enclosu re le14 Ill

- - - - --

ML20077J395

Contents

Text

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

Navigation menu

ML20077J395

Text

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

Navigation menu

Search